NRC Enforcement Policy

January 28, 2013 Revised July 9, 2013 Interim Enforcement Policy (Section 9.2) U. S. Nuclear Regulatory Commission Office of Enforcement Washington, DC 20555-00

NRC ENFORCEMENT POLICY CONTENTS PREFACE... 3 1.0 INTRODUCTION... 4 1.1 Purpose... 5 1.2 Applicability... 5 1.3 Statutory Authority... 6 1.4 Regulatory Framework... 6 1.5 Adequate Protection Standard... 6 1.6 Responsibilities... 7 2.0 NRC ENFORCEMENT PROCESS... 7 2.1 Identification of Violations... 8 2.2 Assessment of Violations... 8 2.2.1 Factors Affecting Assessment of Violations... 8 2.2.2 Traditional Enforcement... 10 2.2.3 Operating Reactor Assessment Program... 11 2.2.4 Exceptions to Using Only the Operating Reactor Assessment Program... 11 2.2.5 Export and Import of Nuclear Material and Equipment... 12 2.2.6 Construction... 12 2.3 Disposition of Violations... 13 2.3.1 Minor Violation... 13 2.3.2 Noncited Violation... 13 2.3.3 Notice of Violation... 15 2.3.4 Civil Penalty... 15 2.3.5 Orders... 23 2.3.6 Demand for Information... 23 2.3.7 Administrative Actions... 24 2.3.8 Reopening Closed Enforcement Actions... 24 2.3.9 Enforcement Guidance Memoranda... 24 2.3.10 Commission Notification and Consultation on Enforcement Actions. 24 2.3.11 Inaccurate and Incomplete Information... 25 2.3.12 Reporting Defects and Noncompliance... 27 2.4 Participation in the Enforcement Process... 27 2.4.1 Predecisional Enforcement Conference... 28 2.4.2 Regulatory Conference... 28 2.4.3 Alternative Dispute Resolution... 28 3.0 USE OF ENFORCEMENT DISCRETION... 29 3.1 Violations Identified during Extended Shutdowns or Work Stoppages... 30 3.2 Violations Involving Old Design Issues... 30 3.3 Violations Indentified Due to Previous Enforcement Actions... 31 3.4 Violations Involving Certain Discrimination Issues... 31 3.5 Violations Involving Special Circumstances... 32 3.6 Use of Discretion in Determining the Amount of a Civil Penalty... 32 1

3.7 Exercise of Discretion To Issue Orders... 33 3.8 Notices of Enforcement Discretion for Operating Power Reactors and Gaseous Diffusion Plants... 33 3.9 Violations Involving Certain Construction Issues... 34 4.0 ENFORCEMENT ACTIONS INVOLVING INDIVIDUALS... 35 4.1 Considerations in Determining Enforcement Actions Involving Individuals... 36 4.2 Notices of Violation and Orders to Individuals... 37 4.3 Civil Penalties to Individuals... 38 4.4 Confirmatory Orders to Individuals... 39 5.0 PUBLIC AVAILABILITY OF INFORMATION REGARDING ENFORCEMENT ACTIONS... 39 6.0 VIOLATION EXAMPLES... 39 6.1 Reactor Operations... 40 6.2 Fuel Cycle Operations... 41 6.3 Materials Operations... 43 6.4 Licensed Reactor Operators... 47 6.5 Facility Construction (10 CFR Part 50 and 52 Licensees and Fuel Cycle Facilities)... 50 6.6 Emergency Preparedness... 51 6.7 Health Physics... 54 6.8 Transportation... 57 6.9 Inaccurate and Incomplete Information or Failure to Make a Required Report... 58 6.10 Discrimination... 63 6.11 Reactor, Independent Spent Fuel Storage Installation, Fuel Facility, and Special Nuclear Material Security... 65 6.12 Materials Security... 66 6.13 Information Security... 70 6.14 Fitness for Duty... 71 6.15 Export and Import Activities...72 7.0 GLOSSARY... 74 8.0 TABLE OF BASE CIVIL PENALTIES... 79 9.0 INTERIM ENFORCEMENT POLICIES... 80 9.1 Enforcement Discretion for Certain Fire Protection Issues (10 CFR 50.48)...80 9.2 Enforcement Discretion for Permanent Implant Brachytherapy Medical Event Reporting (10 CFR 35.3045)... 82 10.0 PAPERWORK REDUCTION ACT STATEMENT and PUBLIC PROTECTION NOTIFICATION..83 2

PREFACE The U.S. Nuclear Regulatory Commission (referred to as the NRC, Commission, or Agency) Enforcement Policy sets forth the general principles governing the NRC s enforcement program and the Commission s expectations regarding the process to be used by the NRC to assess and disposition violations of NRC requirements. However, this is a policy statement and not a regulation. The Commission may deviate from this statement of policy as appropriate under the circumstances of a particular case. The Policy also describes how organizations and individuals subject to NRC enforcement actions can provide input to the process. A glossary is provided which defines specific terms or words as they are used in the context of this Policy. The NRC Enforcement Manual contains specific processes and guidance for implementing this Policy. The guidance provided in the Enforcement Manual has been written to be consistent with this Enforcement Policy. The Enforcement Manual appears on the NRC s public Web site, http://www.nrc.gov (select Public Meetings and Involvement, then Enforcement, then Guidance, then Enforcement Manual or select Electronic Reading Room, ADAMS Documents, and search ADAMS using accession number ML102630150). A compilation of the statutes and materials pertaining to current nuclear regulatory legislation can be found on the NRC webpage. Changes to the NRC Enforcement Policy since it was first published with links to a summary of each change and the Federal Register notice for each change are maintained on the NRC Office of Enforcement (OE) webpage. 3

1.0 INTRODUCTION The mission of the NRC is to license and regulate the Nation s civilian use of byproduct, source, and special nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment. The following are some of the activities that the NRC performs as part of its mission: a. establishing requirements and guidance addressing the possession and use of source, byproduct, and special nuclear material b. licensing applicants to use source, byproduct, and special nuclear material and construct and operate licensed facilities in accordance with NRC requirements and specific license conditions c. promoting the transparency and openness of the NRC s enforcement program for all stakeholders Oversight of licensed activities ensures that licensees are complying with NRC requirements and license conditions. Enforcement is an important part of the NRC s oversight activities. Figure 1. How the NRC Regulates 4

1.1 Purpose The NRC Enforcement Policy supports the NRC s mission to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment. Adequate protection is presumptively assured by compliance with NRC requirements. Compliance with NRC requirements, including regulations, technical specifications, license conditions, and Orders, provides reasonable assurance to the NRC and the public that safety and security are being maintained. The application of this Policy ensures that associated enforcement actions properly reflect the safety or security significance of such violations. Consistent with this objective, the Enforcement Policy endeavors to do the following: a. Deter noncompliance by emphasizing the importance of compliance with NRC requirements. b. Encourage prompt identification and prompt comprehensive correction of violations of NRC requirements. 1.2 Applicability The Enforcement Policy applies to all NRC licensees and applicants, to various categories of nonlicensees, and to individual employees of licensed and nonlicensed entities involved in NRC-regulated activities. These include, but are not limited to the following: a. organizations and individuals holding NRC licenses b. license applicants c. contractors and subcontractors to NRC licensees d. holders of and applicants for various NRC approvals, including, but not limited to: 1. NRC certificates of compliance 2. early site permits 3. standard design certifications 4. quality assurance (QA) program approvals 5. certifications 6. limited work authorizations (LWA) 7. construction authorizations 8. other permits and forms of NRC approval e. vendors supplying safety-related components to NRC licensees f. employees of any of the above Not all NRC requirements apply to all of the categories listed above; however, the Agency will use the Enforcement Policy, as appropriate, to address violations of NRC requirements. 5

It is NRC policy to hold licensees, certificate holders, and applicants responsible for the acts of their employees, contractors, or vendors and their employees, and the NRC may cite the licensee, certificate holder, or applicant for violations committed by its employees, contractors, or vendors and their employees. The NRC may use the term licensee in this Policy to generally refer not only to licensees, but also to certificate holders and applicants. 1.3 Statutory Authority The NRC derives its principal authority to license and regulate the civilian use of nuclear materials from two statutes: (1) the Atomic Energy Act (AEA) of 1954, as amended, which provides broad authority to license and regulate the civilian use of nuclear materials, and (2) the Energy Reorganization Act (ERA) of 1974, as amended, which established the Agency and its major offices. The Administrative Dispute Resolution Act of 1996 (ADRA), 5 U.S.C. 571-584, provides the statutory framework for the Federal Government to use alternative dispute resolution (ADR). 1.4 Regulatory Framework The NRC s enforcement program is governed by its regulations. Title 10 of the Code of Federal Regulations (10 CFR) Part 2, Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders, Subpart B, Procedure for Imposing Requirements by Order, or for Modification, Suspension, or Revocation of a License, or for Imposing Civil Penalties, describes the formal procedures that the NRC uses to implement its enforcement authority. 1.5 Adequate Protection Standard Adequate protection of the public health and safety and assurance of the common defense and security and protection of the environment are the NRC s fundamental regulatory objectives. Compliance with NRC requirements plays a critical role in giving the NRC confidence that safety and security are being maintained. While adequate protection is presumptively assured by compliance with NRC requirements, circumstances may arise where new information reveals that an unforeseen hazard or security issue or security event exists or that a substantially greater potential exists for a known hazard to occur. In such situations, the NRC has the statutory authority to require action by licensees, their employees and contractors, and certificate holders above and beyond existing regulations to maintain the level of protection necessary to avoid undue risk to public health and safety, and to ensure security of materials. The NRC also has the authority to exercise discretion to permit continued operations despite the existence of a noncompliance where the noncompliance is not significant from a risk perspective and does not, in the particular circumstances, pose an undue risk to public health and safety. When noncompliance with NRC requirements occurs, the NRC must evaluate the degree of risk posed by that noncompliance to determine whether immediate action is required. If the NRC determines that the noncompliance itself is of such safety significance that adequate protection is no longer provided, or that the noncompliance was caused by a failure of licensee controls so significant that it calls into question the licensee s ability to ensure adequate protection, the NRC may demand immediate action, up to and including a shutdown or 6

suspension of licensed activities. Based on the NRC s evaluation of noncompliance, the appropriate action could include refraining from taking any action, taking specific enforcement action including the use of civil penalties, issuing Orders, or providing input to other regulatory actions or assessments, such as increased NRC oversight of a licensee s activities. Since some requirements are more important to safety than others, the NRC endeavors to use a risk-informed approach when applying NRC resources to the oversight of licensed activities, including enforcement activities. 1.6 Responsibilities The Executive Director for Operations (EDO) and the principal enforcement officers of the NRC, the Deputy Executive Director for Reactor and Preparedness Programs (DEDR) and the Deputy Executive Director for Materials, Waste, Research, State, Tribal, and Compliance Programs (DEDMRT), have been delegated the authority to approve or issue all escalated enforcement actions. The DEDMRT is responsible to the EDO for NRC enforcement programs. The Director, OE, with some limitations, is delegated the authority by the DEDMRT to approve, sign, and issue all enforcement actions and to oversee and implement the NRC enforcement program. 1 Subject to the oversight and direction of the Director, OE, and with the approval of the DEDMRT, where necessary, the regional offices normally issue notices of violation (NOVs) and proposed civil penalties. Subject to the same oversight as the regional offices, the Directors of the Office of Nuclear Reactor Regulation (NRR), the Office of Nuclear Material Safety and Safeguards (NMSS), the Office of Federal and State Materials and Environmental Management Programs (FSME), the Office of New Reactors (NRO), and the Office of Nuclear Security and Incident Response (NSIR) may also approve, sign, and issue certain enforcement actions as delegated by the Director, OE. The Director, OE, has delegated authority to the Directors of NRR, NMSS, FSME, NRO, and NSIR to issue Orders not related to specific violations of NRC requirements (i.e., nonenforcement-related Orders.) The Chief Financial Officer has been delegated the authority to issue Orders where licensees violate Commission regulations by nonpayment of license and inspection fees. (See NRC Enforcement Manual for a discussion of delegation of enforcement authority.) 2.0 NRC ENFORCEMENT PROCESS The NRC s enforcement process has the following basic steps. a. First, violations must be identified. b. Next, the NRC must assess the severity or significance of the violation. c. Finally, the NRC must disposition the violation. Throughout the process, an organization or individual subject to an NRC enforcement action has multiple opportunities to provide input. 1 OE. See NRC Enforcement Manual for additional information regarding the authority delegated to the Director, 7

2.1 Identification of Violations The enforcement process begins with the identification of violations, either through NRC inspections or investigations, or through a licensee report, or by substantiation of an allegation. All violations are subject to consideration for civil enforcement action; some violations may also be considered for criminal prosecution by the U.S. Department of Justice. After a potential violation is identified, it is assessed in accordance with this Policy. The NRC s enforcement assessment process is fact driven, performance based, and, when appropriate and possible, risk informed. The NRC reviews each case being considered for enforcement action on its own merits to ensure that the severity of a violation is characterized at the level appropriate to the safety significance of the particular violation. 2.2 Assessment of Violations After a violation is identified, the NRC assesses its severity or significance (both actual and potential). Under traditional enforcement, the severity level (SL) assigned to the violation generally reflects the assessment of the significance of a violation, and is referred to as traditional enforcement. For most violations committed by operating power reactor licensees, the significance of a violation is assessed using the significance determination process (SDP) under the Reactor Oversight Process (ROP), as discussed below in Section 2.2.3, Operating Reactor Assessment Program. All other violations will be assessed using traditional enforcement as described in Section 2.2.4, Exceptions to Using Only the Operating Reactor Assessment Program. Power reactor facilities under construction, independent spent fuel storage installations (ISFSI), and nuclear materials facilities are not subject to the SDP and, thus, traditional enforcement will be used for these facilities. 2.2.1 Factors Affecting Assessment of Violations In determining the appropriate enforcement response to a violation, the NRC considers the four specific factors discussed below. Whenever possible, the NRC uses risk information in assessing the safety significance of violations and assigning severity levels. A higher severity level may be warranted for violations that have greater risk, safety, or security significance, while a lower severity level may be appropriate for issues that have lower risk, safety, or security significance. Duration of the violation is also an appropriate consideration in assessing the significance of the violation. a. Whether the violation resulted in actual safety or security consequences. In evaluating actual consequences, the NRC considers issues such as whether the violation resulted in the onsite or offsite releases of radiation or radiation exposures exceeding 10 CFR Part 20, Standards for Protection Against Radiation, regulatory limits, onsite or offsite chemical hazard exposures resulting from licensed or certified activities, accidental criticality, core damage, loss of significant safety barriers, loss of control of radioactive material or radiological emergencies, any violations during an actual General Emergency that prevents offsite response organizations from implementing protective actions (under their emergency plans) to protect public health and safety, or whether the security system did not function as required and, as a result of the failure, a significant event or an event that resulted in an act of radiological sabotage occurred. 8

b. Whether the violation had potential safety or security consequences. In evaluating potential consequences, the NRC considers whether the violation created a credible accident, security failure, or exposure scenario that could potentially have significant actual consequences. For facilities under construction, the NRC considers the actual or potential impact of the violation on the quality of construction and its resulting effect on the safety and security of the facility. c. Whether the violation impacted the ability of the NRC to perform its regulatory oversight function. The NRC considers the safety and security implications of noncompliances that may affect the NRC s ability to carry out its statutory mission. These types of violations include failures to provide complete and accurate information; failures to receive prior NRC approval for changes in licensed activities, when required; failures to notify the NRC of required changes in licensed activities, when required; failures to perform 10 CFR 50.59, Changes, Tests and Experiments, and similar analyses; failures to maintain an up-to-date and accurate FSAR; and failures to comply with reporting requirements, etc. Even inadvertent reporting failures are important because many of the surveillance, quality control, and auditing systems on which both the NRC and its licensees rely to monitor compliance with safety standards are based primarily on complete, accurate, and timely recordkeeping and reporting. The existence of a regulatory process violation does not automatically mean that the issue is significant to safety or security. In determining the significance of a violation, the NRC will consider appropriate factors for the particular regulatory process violation. These factors may include the significance of the underlying issue, whether the failure actually impeded or influenced regulatory action, the level of individuals involved in the failure and the reason why the failure occurred given their position and training, and whether the failure invalidates the licensing basis. Unless otherwise categorized in the violation examples contained in this Policy (i.e., Section 6.0), the severity level of a violation involving the failure to make a required report to the NRC will depend on the significance of and the circumstances surrounding the matter that should have been reported. However, the severity level of an untimely report, in contrast to no report, may be reduced depending on the circumstances. The NRC will not normally cite a licensee for a failure to report a condition or event unless the licensee was actually aware of the condition or event that it failed to report. On the other hand, the Agency will normally cite a licensee for a failure to report a condition or event if the licensee knew of the information to be reported and did not recognize that it was required to make a report. d. Whether the violation involved willfulness. Willful violations are of particular concern because the NRC s regulatory program is based on licensees and their contractors, employees, and agents acting with integrity and communicating with candor. The Commission cannot tolerate willful violations. Therefore, a violation may be considered more significant than the underlying noncompliance if it includes indications of willfulness. Violations with willful aspects will typically be considered for escalated enforcement (i.e., SL I, II, or III). The term willfulness as used in this Policy refers to conduct involving either a careless disregard for requirements or a deliberate violation of requirements or falsification of information. In determining the significance of a violation involving willfulness, the NRC will consider such factors as the position, training, 9

experience level, and responsibilities of the person involved in the violation (e.g., licensee official or nonsupervisory employee), the significance of any underlying violation, the intent of the violator (i.e., careless disregard or deliberateness), and the economic or other advantage, if any, gained as a result of the violation. The relative weight given to each of these factors in the significance assessment will depend on the circumstances of the violation. However, if a licensee refuses to correct a minor violation within a reasonable time such that it willfully continues, the violation should be considered at least more than minor. Licensees are expected to take significant remedial action in responding to willful violations commensurate with the circumstances, such that the action reflects the seriousness of the violation, thereby creating a deterrent effect within the licensee s organization. 2.2.2 Traditional Enforcement Under its traditional enforcement process, the NRC assesses significance by assigning a severity level to all violations by those subject to the NRC s enforcement authority as defined in Section 1.2, Applicability of the Enforcement Policy, and to some violations by operating power reactor licensees. However, the Agency assesses most violations by operating power reactor licensees under the ROP using the SDP (see Section 2.2.3). (Section 6.0 of this Policy provides examples of SL I, II, III, and IV violations in 15 activity areas. These examples are not intended to be exhaustive or controlling.) In recognition that the regulation of nuclear activities in many cases does not lend itself to a mechanistic treatment, judgment and discretion must be exercised in determining the severity levels of the violations and the appropriate enforcement sanctions. This judgment and discretion include the decision to issue an NOV, or to propose or impose a civil penalty and the amount of this penalty, after considering the general principles of this statement of policy and the significance of the violations, as well as the surrounding circumstances. Severity level designations reflect different degrees of significance depending on the activity area in which the severity level is designated. For example, the immediacy of any hazard to the public associated with SL I in reactor operations is not directly comparable to that associated with SL I violations in facility construction. a. SL I violations are those that resulted in or could have resulted in serious safety or security consequences (e.g., violations that created the substantial potential for serious safety or security consequences or violations that involved systems failing when actually called on to prevent or mitigate a serious safety or security event). b. SL II violations are those that resulted in or could have resulted in significant safety or security consequences (e.g., violations that created the potential for substantial safety or security consequences or violations that involved systems not being capable, for an extended period, of preventing or mitigating a serious safety or security event). c. SL III violations are those that resulted in or could have resulted in moderate safety or security consequences (e.g., violations that created a potential for moderate safety or 10

security consequences or violations that involved systems not being capable, for a relatively short period, of preventing or mitigating a serious safety or security event). d. SL IV violations are those that are less serious, but are of more than minor concern, that resulted in no or relatively inappreciable potential safety or security consequences (e.g., violations that created the potential of more than minor safety or security consequences). e. Minor Violations are those that are less significant than a SL IV violation. Minor violations do not warrant enforcement action and are not normally documented in inspection reports. However, minor violations must be corrected. 2.2.3 Operating Reactor Assessment Program The assessment, disposition, and subsequent NRC action related to inspection findings identified at operating power reactors are determined by the ROP, as described in NRC Inspection Manual Chapter (IMC) 0305, Operating Reactor Assessment Program. Inspection findings identified through the ROP are assessed for safety significance using the SDP described in IMC 0609, Significance Determination Process. The SDP uses risk insights, where possible, to assist the NRC staff in determining the safety or security significance of inspection findings identified within the ROP. Inspection findings processed through the SDP, including associated violations, are documented in inspection reports and are assigned one of the following colors, depending on their safety significance a. red inspection findings with high safety or security significance b. yellow inspection findings with substantial safety or security significance c. white inspection findings with low-to-moderate safety or security significance d. green inspection findings with very low safety or security significance With the exceptions noted below in Section 2.2.4, violations associated with ROP inspection findings are not normally assigned severity levels, nor are they normally subject to civil penalties, although civil penalties are considered for any violation that involves actual consequences. 2.2.4 Exceptions to Using Only the Operating Reactor Assessment Program Some aspects of inspection findings and their associated violations at operating power reactors cannot be addressed only through the Operating Reactor Assessment Program. Operating reactor inspection findings are assigned significance and any associated violations involving traditional enforcement are assigned severity levels and can be considered for civil penalties (see IMC 0612). In determining the severity level assigned to such violations, the NRC will consider information in this Policy and the violation examples in Section 6.0 of this Policy, as well as SDP-related information, when available. Typically, the types of violations dispositioned using traditional enforcement include the following: a. violations that resulted in actual safety or security consequences (as described in Section 2.2.1.a) 11

b. violations that may impact the ability of the NRC to perform its regulatory oversight function (as described in 2.2.1.c) c. violations involving willfulness (as described in Section 2.2.1.d) d. violations of NRC requirements for which there are no associated SDP performance deficiencies (e.g., a violation of TS which is not a performance deficiency.) These violations are normally dispositioned using discretion, similar to that described in Section 3.2 of this Policy. 2.2.5 Export and Import of Nuclear Equipment and Material The NRC will normally take enforcement action for violations of the Agency s export and import requirements in 10 CFR Part 110, Export and Import of Nuclear Equipment and Material, for radioactive material and equipment within the scope of the NRC s export and import licensing authority (10 CFR 110.8, 110.9, and 110.9a) for (1) completeness and accuracy of information, (2) reporting and recordkeeping requirements (10 CFR 110.23, 110.26, 110.50, and 110.54), and (3) adherence to general and specific licensing requirements (10 CFR 110.20-27 and 10 CFR 110.50). 2.2.6 Construction In accordance with 10 CFR 50.10, no person may begin the construction of a production or utilization facility on a site on which the facility is to be operated until that person has been issued either a construction permit under 10 CFR Part 50, a combined license under 10 CFR Part 52, an early site permit authorizing the activities under 10 CFR 50.10(d), or a limited work authorization under 10 CFR 50.10(d). In an effort to preclude unnecessary regulatory burden, while maintaining safety, the Changes during Construction (CdC) Process, as developed in Interim Staff Guidance (ISG)- 025, permits the licensee to proceed with the installation and testing of structures, systems or components different from the current licensing basis while the license amendment request (LAR) is under NRC review. Any activities undertaken under the CdC process are at the risk of the licensee, and the licensee is obligated to return to the current licensing basis (CLB) if the related LAR is subsequently not approved by the NRC. Failure to timely restore the CLB may be subject to separate enforcement, such as an order, a civil penalty, or both. In accordance with 10 CFR 70.23(a)(7) and 10 CFR 40.32(e), commencement of construction before the NRC finishes its environmental review and issues a license for processing and fuel fabrication, conversion of uranium hexafluoride, or uranium enrichment facility construction and operation is grounds for denial to possess and use licensed material in the plant or facility. Additionally, in accordance with10 CFR 70.23(b), failure to obtain Commission approval for the construction of the principal structures, systems, and components of a plutonium processing and fuel fabrication plant before the commencement of construction may also be grounds for denial of a license to possess and use special nuclear material. 12

2.3 Disposition of Violations This section describes the various ways that the NRC can disposition violations. 2.3.1 Minor Violation Violations of minor safety or security concern generally do not warrant enforcement action or documentation in inspection reports but must be corrected. Examples of minor violations can be found in the NRC Enforcement Manual and in IMC 0612, Power Reactor Inspection Reports (Appendix E, Examples of Minor Issues ). Guidance for documenting minor violations can be found in the NRC Enforcement Manual; IMC 0610, Nuclear Material Safety and Safeguards Inspection Reports ; IMC 0612; IMC 0613, Documenting 10 CFR Part 52 Construction and Test Inspections ; IMC 0616, Fuel Cycle Safety and Safeguards Inspection Reports ; and IMC 0617, Vendor and Quality Assurance Implementation Inspection Reports. 2.3.2 Noncited Violation SL IV violations and violations associated with green ROP findings (for operating reactors) are normally dispositioned as noncited violations (NCVs). Inspection reports or inspection records document NCVs and briefly describe the corrective action the licensee or nonlicensee has taken or plans to take, if known. Licensees and nonlicensees are not required to provide written responses to NCVs; however, they may provide a written response if they disagree with the NRC s description of the NCV or dispute the validity of the NCV. Typically, all of the criteria in either 2.3.2.a or b must be met for the disposition of a violation as an NCV. For all SL IV violations identified by the NRC at fuel cycle facilities (under construction or in operation) in accordance with 10 CFR Part 70 or 10 CFR Part 40 and reactors under construction in accordance with 10 CFR Part 50 or 10 CFR Part 52, before the NRC determines that an adequate corrective action program has been implemented, the NRC normally issues a Notice of Violation. Until the determination that an adequate corrective action program has been implemented, NCVs may be issued for SL IV violations if the NRC has determined that the applicable criteria in 2.3.2.b. below are met. For reactor licensees, after the NRC determines that an adequate corrective action program has been implemented, the NRC will normally issue an NCV in lieu of an SL IV violation, whether that violation is identified by the licensee or the NRC. a. Licensees and Nonlicensees with a Corrective Action Program 2 1. The licensee or nonlicensee must place the violation into a corrective action program to restore compliance and address recurrence. 2. The licensee or nonlicensee must restore compliance (or demonstrate objective evidence of plans to restore compliance) within a reasonable period of time (i.e., in a timeframe commensurate with the significance of the violation) after a violation is identified. 2 The NRC will credit a formal corrective action program that has been inspected and found to meet regulatory guidance, industry standards, or both. 13

3. The violation must either not be repetitive 3 as a result of inadequate corrective action, or, if repetitive, the repetitive violation must not have been identified by the NRC. This criterion does not apply to violations associated with green ROP findings. 4. The violation must not be willful. Notwithstanding willfulness, an NCV may still be appropriate in the following circumstances: (a) (b) (c) (d) The licensee or nonlicensee identified the violation and promptly provided the information concerning the violation, if not required to be reported, to appropriate NRC personnel, such as a resident inspector or regional branch chief. The violation involved the acts of an individual in a low-level position within the licensee s or nonlicensee s organization (and not a licensee or nonlicensee official as defined in Section 7.0, Glossary ). The violation appears to be the isolated action of the employee without management involvement, and the violation was not caused by lack of management oversight as evidenced by either a history of isolated willful violations or a lack of adequate audits or supervision of employees. The licensee or nonlicensee took significant remedial action commensurate with the circumstances. This action demonstrated the seriousness of the violation to other employees and contractors, thereby creating a deterrent effect within the licensee s or nonlicensee s organization. The approval of the Director, OE, is required to disposition willful violations as NCVs. b. All Other Licensees and Nonlicensees 1. The licensee or nonlicensee identified the violation. 4 2. The licensee or nonlicensee corrected or committed to correcting the violation within a reasonable period of time by specific corrective action committed to by the end of the inspection, including immediate corrective action and comprehensive action to prevent recurrence. 3 A violation is considered repetitive if it could reasonably be expected to have been prevented by the licensee's corrective action for a previous violation. In addition, a violation is considered repetitive if a previous licensee finding occurred within the past 2 years of the inspection at issue, or the period between the last two inspections, whichever is longer. 4 An NOV is warranted when a licensee or nonlicensee identifies a violation as a result of an event where the root cause of the event is obvious or the licensee had prior opportunity to identify the problem but failed to take action that would have prevented the event. Disposition as an NCV may be warranted if the licensee or nonlicensee demonstrated initiative in identifying the violation s root cause. 14

3. The violation is not repetitive as a result of inadequate corrective action. 4. The violation is not willful. Notwithstanding willfulness, an NCV may still be appropriate if it meets the criteria in Section 2.3.2.a.4 above. The approval of the Director, OE, is required to disposition willful violations as NCVs. 2.3.3 Notice of Violation A Notice of Violation (NOV) (see 10 CFR 2.201, Notice of Violation ) is a written notice setting forth one or more violations of a legally binding requirement and normally requires the recipient to provide a written response describing (1) the reasons for the violation or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken by the licensee or other person and the results achieved, (3) the corrective steps that will be taken, and (4) the date when full compliance will be achieved. The NRC may waive all or portions of a written response to the extent that relevant information has already been provided to the NRC in writing or documented in an NRC inspection report or inspection record. The NRC may require responses to NOVs to be under oath; however, normally, responses under oath will be considered necessary only for SL I, II, or III violations; violations assessed using the SDP as white, yellow, or red; or violations of NRC Orders. A civil penalty may be issued in conjunction with an NOV. 2.3.4 Civil Penalty A civil penalty (see 10 CFR 2.205, Civil Penalties ) is a monetary penalty that the NRC may impose for violations of (1) certain specified licensing provisions of the AEA or supplementary NRC rules or Orders, (2) any requirement for which a license may be revoked, (3) reporting requirements under Section 206 of the ERA, or (4) any NRC rule adopted under Section 147 of the AEA with respect to safeguards information. Based on the circumstances of a specific case, the NRC may increase a civil penalty where application of the guidance in this Policy would normally result in a zero penalty or a base civil penalty, to ensure that the proposed civil penalty reflects the safety significance of the case. The NRC s policy of imposing graduated civil penalties generally takes into account the gravity of the violation as the primary consideration and the ability to pay as a secondary consideration. Thus, operations involving greater nuclear material inventories, significantly higher consequences resulting from a release or exposure to radioactive material, and consequences to the public and workers receive higher civil penalties. Regarding the secondary factor of the ability of various classes of licensees to pay the civil penalties, it is not the NRC s intention that the economic impact of a civil penalty be so severe that it adversely affects a licensee s ability to safely conduct licensed activities or puts a licensee out of business (Orders, rather than civil penalties, are used when the NRC s intent is to suspend or terminate licensed activities). Civil penalties are considered for all SL I, II, and III violations. The civil penalty assessment process described in this section and depicted in Figure 2 should be followed to determine the appropriateness of a civil penalty for any escalated enforcement action. Notwithstanding the outcome of the normal civil penalty assessment process, discretion, as discussed in this section 15

and in Section 3.6, Use of Discretion in Determining the Amount of a Civil Penalty, may be exercised by either escalating or mitigating the amount of the civil penalty. Violations assessed under the SDP normally are not considered for civil penalties. However, civil penalties are considered for violations associated with inspection findings evaluated through the ROP s SDP that involve actual consequences. The NRC may exercise discretion and assess a separate violation and attendant civil penalty up to the statutory limit for each day the violation continues (i.e., daily civil penalties). The NRC may exercise this discretion when a licensee was aware of a violation of at least moderate significance (i.e., at least a SL III) and had a clear opportunity to prevent, identify, and correct the violation but failed to do so. In evaluating whether daily civil penalties are appropriate, the NRC will consider such factors as whether the violation resulted in actual consequences to public health and safety or to the common defense and security, the safety significance of the violation, whether the violation was repetitive because of inadequate corrective actions, the degree of management culpability in allowing the violation to continue or in not precluding it, the responsiveness of the licensee once the violation and its significance were identified and understood, whether the continuing violation was willful, and the duration of the violation. These evaluation factors are not necessarily of equal significance; therefore, for each case, the NRC will weigh the relative importance of each contributing factor, as well as any extenuating circumstances, to determine whether it is appropriate to use daily civil penalties. When the NRC determines that the use of daily civil penalties is appropriate as part of an enforcement action, the Agency will assess a base civil penalty for the first day of the violation in accordance with the civil penalty assessment process discussed in this section and Section 8.0, Table of Base Civil Penalties, of the Policy. Then, to determine the total civil penalty for the continuing violation, the NRC will supplement the base civil penalty determination with a daily civil penalty for some or all of the days the violation continues. The NRC will determine the amount of the daily civil penalty on a case-by-case basis after considering the factors noted in the preceding paragraph and any relevant past precedent for similar violations. The daily civil penalty may be less than the maximum statutory daily limit in effect at the time of the violation. The NRC considers civil penalties for violations associated with loss of regulated material (i.e., the NRC s lost source policy). The loss of NRC-regulated material is a significant regulatory and security concern because of the potential unauthorized possession or use of the material and because of the potential for overexposure to members of the public from its misuse. Such violations may include but are not limited to the loss, abandonment, improper transfer, or improper disposal of a device, source, or other form of regulated material. Notwithstanding the normal civil penalty assessment process, in cases where a licensee has lost its regulated radioactive material, the NRC may exercise discretion and impose a civil penalty. However, the Agency may mitigate or escalate a civil penalty amount based on the merits of a specific case. When appropriate, the NRC may consider, for example, information on the estimated or actual cost of authorized disposal and the actual consequences of the material remaining out of the control of the licensee, as well as any effect on radiation workers or the environment. Normally, the NRC will not apply the lost source policy to generally licensed 16

devices that are not required to be registered in accordance with 10 CFR 31.5(c)(13)(i). The NRC will continue to apply the normal Enforcement Policy in those cases where licensees have lost control of regulated material. The Commission recognizes that violations occur in a variety of activities and have varying impacts; therefore, the civil penalty Tables A and B in Section 8.0 of this Policy contain graduated sanctions based on the severity level of the violation. The tables present the base civil penalty (i.e., normal civil penalty, for any severity level violation for each type of licensee before consideration of factors to either escalate or use discretion to increase or decrease those amounts). The civil penalty amounts applied should be those in effect at the time of the violation. The flow chart (Figure 2) presented below is a graphic representation of the civil penalty assessment process. The civil penalty assessment process considers four decision points. Although each of these decision points may have several associated considerations for any given case, the outcome of the assessment process for each violation or problem, absent the exercise of discretion, is limited to one of the following three results: no civil penalty, a base civil penalty, or a base civil penalty escalated by 100 percent. The four decision points are the following: a. Did the licensee have any previous escalated enforcement action (regardless of the activity area) within the past 2 years of the inspection at issue, or the period between the last two inspections, whichever is longer? When the NRC determines that a nonwillful SL III violation or problem has occurred, and the licensee has not had any previous escalated actions (regardless of the activity area) during the past 2 years or two inspections, whichever period is longer, the NRC will consider whether the licensee s corrective action for the present violation or problem is reasonably prompt and comprehensive (see the discussion under Section 2.3.4.c, below). Using 2 years as the 17

basis for assessment is expected to cover most situations, but considering a slightly longer or shorter period may be warranted based on the circumstances of a particular case. For a licensee-identified violation or an event, the starting point of this period is when the licensee becomes aware that a problem or violation exists that requires corrective action. For an NRC-identified violation, the starting point is when the NRC put the licensee on notice of the need to take corrective action for the previous violation, which could be during the inspection, at the inspection exit meeting, or as part of post inspection communication with the licensee. The 2 year period typically ends on the date of the second violation. b. Should the licensee be given credit for actions related to identification of the violation? A stated purpose of this Policy is to encourage prompt identification of violations of NRC requirements. While the decision regarding credit for identification can become complicated, the overarching consideration is whether the NRC should give credit for a licensee s efforts to identify the violation. It is the responsibility of the licensee to bring information on efforts to identify the violation to the attention of the NRC. The NRC will not undertake an inquiry to obtain information on whether identification credit is warranted. 1. The civil penalty assessment should normally consider the factor of identification, in addition to corrective action (see the discussion in Section 2.3.4.c, below). In these circumstances, the NRC should consider whether the licensee should be given credit for actions related to identification when any of the following conditions exist: (a) (b) (c) the violation is a SL I or II the violation is a willful SL III the licensee has been issued at least one other escalated action during the past 2 years or 2 inspections, whichever is longer. In each case, the decision should be focused on identification of the problem requiring corrective action. In other words, although giving credit for identification and corrective action should be separate decisions, the concept of identification presumes that the identifier recognizes the existence of a problem and understands that corrective action is needed. The decision on identification requires considering all the circumstances of identification including the following: (a) (b) (c) whether the problem requiring corrective action was identified by the NRC, identified by the licensee, or revealed through an event whether prior opportunities existed to identify the problem requiring corrective action, and if so, the age and number of those opportunities whether the problem was revealed as the result of a licensee self-monitoring effort, such as conducting an audit, a test, a surveillance, a design review, or troubleshooting 18

(d) (e) (f) (g) for a problem revealed through an event, the ease of discovery and the degree of licensee initiative in identifying the root cause of the problem and any associated violations for NRC-identified issues, whether the licensee would likely have identified the issue in the same time period if the NRC had not been involved for NRC-identified issues, whether the licensee should have identified the issue (and taken action) earlier for cases in which the NRC identified the overall problem requiring corrective action (e.g., a programmatic issue), the degree of licensee initiative or lack of initiative in identifying the problem or problems requiring corrective action 2. Although some cases may consider all of the above factors, the importance of each factor will vary based on the type of case, as discussed in the following general guidance: (a) (b) Licensee Identified When a problem requiring corrective action is licensee identified (i.e., identified by the licensee before the problem results in an event), the NRC should normally give the licensee credit for actions related to identification, regardless of whether prior opportunities existed to identify the problem. Identified through an Event When a problem requiring corrective action is identified through an event (i.e., the problem is self-revealing), the decision as to whether to give the licensee credit for actions related to identification normally should consider the ease of discovery, whether the event occurred as the result of a licensee s self-monitoring effort (i.e., whether the licensee was looking for the problem ), the degree of licensee initiative in identifying the problem or problems requiring corrective action, and whether prior opportunities existed to identify the problem. Any of these considerations may be overriding if particularly noteworthy or particularly egregious. For example, if the event occurred as the result of conducting a surveillance or similar self-monitoring effort (i.e., the licensee was looking for the problem), the licensee should normally be given credit for identification. Even if the problem was easily discovered (e.g., revealed by a large spill of liquid), the NRC may choose to give credit because noteworthy licensee effort was exerted in discovering the root cause and associated violations, or simply because no prior opportunities, for example, procedural cautions, post-maintenance testing, quality control failures, readily observable parameter trends, or 19